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  • 2014:18 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 2, 3 and 4

    The analytical tools, which are fuel rod computer codes, that Quantum Technologies AB use and develop, contain models of several of the phenomena that are acting on the nuclear fuel (cladding temperature, fission gas driven pressure, strain and stress in the cladding, rod rupture, etc.) and how the separate effects interact in the complex integrated manner. The codes are under constant...

    Innehållstyp: Publikationer
  • 2012:07 Implementation of the Master Curve method in ProSACC

    Cleavage fracture toughness data display normally large amount of statistical scatter in the transition region. The cleavage toughness data in this region is specimen size-dependent, and should be treated statistically rather than deterministically. The Master Curve (MC) methodology is a procedure for mechanical testing and statistical analysis of fracture toughness of ferritic steels in the...

    Innehållstyp: Publikationer
  • 2019:15 3D Thermo-Mechanical Coupled Modelling of Thermo-Seismic Response of a Fractured Rock Mass related to the Final Disposal of Spent Nuclear Fuel and Nuclear Waste in Hard Rock

    SSM perspective Background When assessing the long-term safety of a repository for spent nuclear fuel it is important to consider future earthquakes. Previous studies by Yoon et al. (2014, SSM Report 2014:59) and (2016, SSM Report 2016:23) investigated the fracture responses due to heat and earthquakes at major deformation zones using a 2D thermo-mechanical coupled model that uses a Particle...

    Innehållstyp: Publikationer
  • 2019:24 SSM's external experts' review of SKB's analysis of long-term safety of 1BMA (SFR)

    SSM perspective Background Fractures in the concrete barrier of the rock vault 1BMA in the final repository for low and intermediate level waste (SFR) have been observed. The Swedish Radiation Safety Authority (SSM) enforced Swedish Nuclear Fuel and Waste Management Company (SKB) to assess the long-term radiological consequences of 1BMA (SSM2015-2432-26) given the present state of the rock...

    Innehållstyp: Publikationer
  • 2007:45 Icke-spridning och kärnämneskontroll

    Det kompendium som nu föreligger kommer att användas både inom och utom landet som kursmaterial vid utbildningar. Det är delvis ett resultat av ESARDA:s (European Safeguards Research and Development Association) arbetsgrupp TKM (Training and knowledge management) som årligen utbildar studenter från hela Europa. Avsikten är även att använda det i samband...

    Innehållstyp: Publikationer
  • 2003:46 Cerenkov Characteristics of PWR Assemblies Using a Prototype DCVD With a Back-Illuminated CCD

    Canadian and Swedish Safeguard Support Programs J.D. Chen, A.F. Gerwing, R. Maxwell, M. Larsson, K. Axell, L. Hildingsson, B. Lindberg, E. Sundkvist. November 2003 SKI English...

    Innehållstyp: Publikationer
  • 2010:46 Development of the PRO-LOCA Probabilistic Fracture Mechanics Code, MERIT Final Report

    The MERIT project has been an internationally financed program with the main purpose of developing probabilistic models for piping failure of nuclear components and to include these models in a probabilistic code named PRO-LOCA. The principal objective of the project has been to develop probabilistic models for piping failure of nuclear components and to include these models in a...

    Innehållstyp: Publikationer
  • 2010:42 Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3

    In the SSM regulation SSMFS 2008:13, it is stated that the selection of locations for inspection of mechanical components shall be based upon the risk for core damage or the risk of release of radioactive substances. Both qualitative and quantitative measures of the relative risk are allowed to be used. So far only the PWRs in Sweden are using a quantitative procedure to evaluate the risk...

    Innehållstyp: Publikationer
  • 2010:16 Guidance to Risk-Informed Evaluation of Technical Specifications using PSA

    No guidance documents for risk-informed analysis and assessment of changes in Limiting Conditions for Operation (LCO:s) in TS (Technical Specifications) have been available in the Nordic countries. In the U.S. several guidance documents, primarily developed by the owners groups for PWRs and BWRs, exist. Guidance for analysis of TS changes in this report generally follows the U.S. Regulatory...

    Innehållstyp: Publikationer
  • 2010:03 Forskningsstrategi 2010-2014

    Strålsäkerhetsmyndighetens uppdrag omfattar frågor om skydd av människors hälsa och miljön mot skadlig verkan av joniserande och icke-joniserande strålning, säkerhet i kärnteknisk verksamhet samt nukleär icke-spridning. För att myndigheten ska kunna utföra uppdraget behöver ny kunskap kontinuerligt tillföras verksamheten. Genom...

    Innehållstyp: Publikationer